EP3984046B1 - Reactor pressure vessel cooling system - Google Patents
Reactor pressure vessel cooling system Download PDFInfo
- Publication number
- EP3984046B1 EP3984046B1 EP20737358.0A EP20737358A EP3984046B1 EP 3984046 B1 EP3984046 B1 EP 3984046B1 EP 20737358 A EP20737358 A EP 20737358A EP 3984046 B1 EP3984046 B1 EP 3984046B1
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- EP
- European Patent Office
- Prior art keywords
- cooling
- medium
- reactor pressure
- pressure vessel
- vessel
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
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- 238000001816 cooling Methods 0.000 title claims description 80
- 239000002826 coolant Substances 0.000 claims description 123
- 239000007788 liquid Substances 0.000 claims description 5
- 238000009434 installation Methods 0.000 claims 1
- 239000000498 cooling water Substances 0.000 description 64
- 238000005086 pumping Methods 0.000 description 10
- 239000011162 core material Substances 0.000 description 9
- 239000000463 material Substances 0.000 description 8
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 7
- 230000000694 effects Effects 0.000 description 5
- 239000012530 fluid Substances 0.000 description 5
- 230000017525 heat dissipation Effects 0.000 description 3
- 239000000941 radioactive substance Substances 0.000 description 3
- 239000003570 air Substances 0.000 description 2
- 230000006378 damage Effects 0.000 description 2
- 238000001704 evaporation Methods 0.000 description 2
- 230000008020 evaporation Effects 0.000 description 2
- 230000000717 retained effect Effects 0.000 description 2
- 238000010521 absorption reaction Methods 0.000 description 1
- 238000009825 accumulation Methods 0.000 description 1
- 239000012080 ambient air Substances 0.000 description 1
- 238000006243 chemical reaction Methods 0.000 description 1
- 238000002485 combustion reaction Methods 0.000 description 1
- 230000002950 deficient Effects 0.000 description 1
- 230000001419 dependent effect Effects 0.000 description 1
- 230000006866 deterioration Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 230000003628 erosive effect Effects 0.000 description 1
- 230000002349 favourable effect Effects 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 230000020169 heat generation Effects 0.000 description 1
- 238000011835 investigation Methods 0.000 description 1
- 230000014759 maintenance of location Effects 0.000 description 1
- 239000000155 melt Substances 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 238000004321 preservation Methods 0.000 description 1
- 230000001502 supplementing effect Effects 0.000 description 1
Images
Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
- G21C15/182—Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Definitions
- the invention relates to a reactor pressure vessel cooling system of a nuclear facility with a closed containment, with a reactor pressure vessel being arranged inside the containment, with a cooling medium collection area for receiving a cooling medium being located within the containment, and with so much cooling medium being present between the containment and the reactor pressure vessel that the reactor pressure vessel is at least partially surrounded by the cooling medium.
- a nuclear reactor In order to ensure maximum safety even in the event of an accident, a nuclear reactor is surrounded by a hermetically sealed safety vessel or containment, which means that, for example, in the event of a break in active systems, in the event of defective fuel rods or in the event of a Chain reaction, the radioactive substances that may be released cannot escape into the environment, but rather are retained in the containment.
- security containers can be implemented, for example, in the form of a concrete bell.
- a cooling medium collection area or a so-called reactor sump or a sump area in which, in the event of a possible incident, radioactively contaminated cooling water escaping from a leaking cooling system, for example, is collected, cooled if necessary and fed back to the cooling system or the reactor core or other systems.
- a nuclear reactor is arranged in a cooling medium collection area, which is flooded with cooling water in the event of an accident in order to achieve increased cooling of the nuclear reactor, with the radioactively contaminated cooling water collecting in the reactor sump also having to be cooled here, for example with a Safety container cooling system according to the German patent application DE 10 2017 008 254 A1 .
- the prior art is still from the document U.S. 2010/260302 A1 known.
- a reactor pressure vessel cooling system of the type mentioned at the outset.
- a pumping device is arranged in the containment and is completely immersed in the cooling medium, that cooling medium is supplied to a nozzle arrangement by the pumping device, that the nozzle device has a number of cooling medium nozzles and that the cooling medium nozzles are arranged such that the cooling medium flowing through the cooling medium nozzles generates a forced cooling medium flow in the cooling medium of the cooling medium collecting area, through which forced cooling medium flow a surface area of the reactor pressure vessel flows.
- the basic idea of the invention is, instead of the previous natural convection alone, to now generate a forced flow in the cooling medium by means of a pump device, which is directed to a surface area of the reactor pressure vessel and in this way increases the heat transport from the reactor pressure vessel into the cooling medium in comparison to the previously known cooling systems.
- the cooling capacity or the cooling of the reactor pressure vessel in the event of an accident is improved.
- the safety vessel also referred to as containment or confinement, will be at least partially flooded with cooling medium, with the cooling medium forming the cooling medium collection area.
- the pumping device is preferably arranged geodetically below a planned liquid level of the cooling medium after the flooding in the containment.
- the pumping device is arranged in the cooling medium collection area, which is flooded during operation, so that the pumping device is completely immersed in cooling medium and is operated as a submersible pump or sump pump. Although this is not absolutely necessary, it improves the pumping properties of the pump device.
- the reactor pressure vessel cooling system is an accident scenario in which a core meltdown has occurred in the nuclear reactor, i.e. inside the reactor pressure vessel. Previous cooling systems or emergency cooling systems have mastered this Incident not permanent.
- the core meltdown namely collects in the geodetically lower area of the reactor pressure vessel and unfolds there a comparatively strong development of heat, which stresses the material or the wall of the reactor pressure vessel in terms of material technology.
- an active cooling system ie a cooling system with a forced flow, is disclosed which applies cooling medium in particular to the region of the reactor pressure vessel wall directly affected by the heat generation in the reactor pressure vessel.
- the cooling medium is often cooling water or borated cooling water.
- the relevant wall area is correspondingly cooled, so that correspondingly more heat is transported away from the reactor pressure vessel. In this way, an impermissible rise in temperature of the reactor pressure vessel wall is avoided, which would possibly also be associated with a loss of wall material of the reactor pressure vessel. A required wall thickness of the reactor pressure vessel wall is thus advantageously retained. The maximum permissible heat flow over the reactor pressure vessel wall is also not reached. Both effects contribute to maintaining the integrity or stability of the reactor pressure vessel.
- the forced flow can basically be used in two possible ways. On the one hand in such a way that the cooling medium emerging from the cooling medium nozzles is jetted directly in the direction of the surface of the reactor pressure vessel to be cooled. On the other hand in the way that the cooling medium emerging from the cooling medium nozzles is jetted in a direction other than in the direction of the surface of the reactor pressure vessel to be cooled, preferably in the geodetically downward direction.
- a particularly favorable direction for the second type of forced flow can be determined by empirical investigations in individual cases for an existing reactor pressure vessel geometry or calculated on the computer using a flow model for an existing reactor pressure vessel geometry. This second type should also be called indirect forced flow.
- An alternative configuration of the reactor pressure vessel cooling system is characterized in that the cooling medium nozzles are completely surrounded by cooling medium. In this way it is ensured that a forced flow is generated with the most advantageous possible cooling effects.
- the volume flow of the forced flow is namely when the cooling medium nozzles are completely immersed in the cooling medium, since the surrounding cooling medium is entrained by the cooling medium jet from the cooling medium nozzles and thus causes an increased volume flow and thus also an increased cooling effect on the reactor pressure vessel.
- At least some of the cooling medium nozzles are aligned in such a way that the cooling medium exiting through them is guided in the direction of the reactor pressure vessel.
- a specific surface area of the reactor pressure vessel which is directly affected, for example, by the heat generated by a core meltdown, can be cooled in a targeted manner, namely by direct jetting with cooling water.
- a reactor pressure vessel cooling system which provides that at least some of the cooling medium nozzles are aligned in such a way that the cooling medium exiting through them is guided essentially downwards in the geodetic direction, and that the resulting indirect forced flow flows against the reactor pressure vessel.
- a particularly simple and robust forced cooling is realized, with the indirect forced flow being able to cool practically the entire surface area of the reactor pressure vessel that is immersed in the cooling medium.
- the cooling effect is given in the existing cooling medium, regardless of the liquid level of the cooling medium in the containment.
- the cooling medium nozzles are arranged in at least one nozzle ring.
- the at least one nozzle ring is arranged around the geodetically lower base area of the reactor pressure vessel and/or a central central area of the reactor pressure vessel located geodetically above the base area.
- certain surface areas of the reactor pressure vessel can be specifically irradiated with cooling medium and also the quantity or the volume flow of cooling medium determined for specific surface areas by the design of the cooling medium nozzles and the at least one nozzle ring.
- individual coolant nozzles or groups of coolant nozzles have a different design, so that a different amount of coolant flows through the coolant nozzles at a pressure predetermined by the pump device.
- a further reactor pressure vessel cooling system provides that cooling medium is routed through the pumping device to further cooling medium nozzles, by means of which further cooling medium nozzles cooling medium can be sprayed geodetically above the cooling medium in the containment as required into the air in the containment. In this way, additional heat is extracted from the area in the containment above the cooling medium and absorbed by the cooling medium.
- the reactor pressure vessel area above the cooling medium can also be sprayed with cooling medium in this way. This further increases the cooling capacity for the reactor pressure vessel.
- a cooling medium heat exchanger system is arranged between the pump device and the cooling medium nozzles, by means of which heat can be transported from inside the containment to outside the containment.
- a cooling medium heat exchanger system is arranged between the pump device and the cooling medium nozzles, by means of which heat can be transported from inside the containment to outside the containment.
- an additional cooling system or recooling system for the cooling medium is created that works in addition to the heat exchangers of a containment cooling system that are present anyway.
- the re-cooling capacity of the cooling medium is further increased.
- the temperature of the cooling medium which is supplied to the cooling medium nozzles through the feed line is reduced by at least one cooling medium heat exchanger of the cooling medium heat exchanger system, so that in any case an improved cooling capacity for the reactor pressure vessel wall is also achieved.
- cooling medium heat exchanger system is arranged geodetically above the cooling medium collecting area, so that the cooling medium heat exchanger system is arranged geodetically above the cooling medium during operation.
- the containment has a pressure relief device which works together with a coolant supply device, which coolant supply device introduces cooling medium into the containment from a point outside of the containment in a quantity such as through the pressure relief device cooling medium from inside the containment got outside.
- a coolant supply device introduces cooling medium into the containment from a point outside of the containment in a quantity such as through the pressure relief device cooling medium from inside the containment got outside.
- the vaporized cooling water is routed through the pressure relief device to the outside of the containment, optionally with the interposition of a filter system for retaining radioactive substances.
- the amount of cooling medium reduced by evaporation is supplemented accordingly by the supply of cooling medium from a point outside the containment into the containment.
- jet pumps, centrifugal pumps, volumetric pumps or piston pumps come into consideration as pumps or pump elements for the pump device. These are preferably driven by electrically or hydraulically operated drives or by a hydraulically operated turbine.
- a drive fluid of the hydraulically operated drive or the hydraulically operated turbine is delivered by a pump that is arranged outside of the containment vessel. This ensures that the pump can be operated outside the area affected by the incident.
- the pump it is also possible to design the pump as a conventionally driven pump, for example as an electrically driven pump or as a pump driven by an internal combustion engine. Corresponding redundancies for the pump can then also be implemented in a particularly simple manner.
- the drive fluid is the cooling medium for the cooling medium heat exchanger system.
- the cooling capacity of the reactor pressure vessel cooling system is further increased without requiring an additional pump for the cooling medium heat exchanger system.
- All the configurations of the reactor pressure vessel cooling system mentioned can be designed in such a way that the cooling of the reactor pressure vessel is increased in such a way that it is also sufficient to transport away the heat generated in the nuclear reactor, for example in the event of a core meltdown, even over a period of, for example, 3 to 6 months or even years , so that the integrity of the reactor pressure vessel is permanently maintained.
- FIG. 1 shows in an example a first reactor pressure vessel cooling system 10 for a nuclear reactor of a nuclear power plant, in which a reactor pressure vessel 14 is arranged in a containment 12.
- the sketch according to the figure shows a system situation in which a core meltdown has occurred in the reactor pressure vessel 14, which is shown by a collection area 16 of the melt products which collect in the geodetically lower area of the reactor pressure vessel 14.
- the surface of the collecting area 16 is indicated by a first surface symbol 18 .
- a space between the containment 12 and the reactor pressure vessel 14 is flooded with, for example, cooling water as a cooling medium through a containment cooling system, so that a cooling medium collection area 20 is formed, the fill level of which in the containment 12 is indicated by a second surface symbol 22.
- the containment cooling system is not shown in this figure.
- its task is the heat given off by the nuclear reactor to the cooling water, for example the decay heat of the nuclear fuel, from the cooling water, for example by means of corresponding Include heat exchanger and transport to a location outside of the containment vessel 12.
- the containment cooling system is not designed to handle a meltdown accident. It only serves to transport the heat present in the cooling water out of the containment vessel 12 .
- a pumping device 24 which is completely surrounded by cooling water is arranged in the cooling water collecting area 22 as the cooling medium collecting area.
- The. Pump device 24 has a centrifugal pump 26 as a pump element and a hydraulic drive turbine 28, which are arranged on a common shaft.
- a pump device is for example in the German patent application DE 10 2018 009 260 A1 explained in more detail. It is also within the scope of the invention to replace the pump part with any other type of pump as well as the drive part with any other type of drive.
- the drive turbine 28 is driven by a drive fluid, namely water, which is supplied through a water line 30 by means of a pump 32 from an area outside the containment vessel 12 .
- the line 30 leads the drive fluid out of the containment vessel 12 again.
- the centrifugal pump 26 acts as a sump pump and draws cooling water out of it Environment in the cooling water collection area 20 and conveys this via a supply line 34 to a nozzle head 36.
- a nozzle device thus has the supply line 34 and the nozzle head 36 in the example shown.
- the nozzle head 36 is directed at the geodetically lowest point of the reactor pressure vessel 14 in such a way that the outflowing cooling water flows against this point and such a forced flow is formed in the cooling water.
- the forced flow introduced into the cooling water by the nozzle device flows geodetically essentially from bottom to top, so that the forced flow flows in particular along a surface of a bottom area of reactor pressure vessel 14, which bottom area extends approximately to first surface symbol 18.
- the bottom area has approximately the shape of a dished bottom.
- a middle area of the reactor pressure vessel 14 whose part of the surface that is in contact with the cooling water is also surrounded by the forced flow.
- the design of the nozzle head 36 is not limited to a single nozzle.
- the nozzle head 36 can namely have a large number of individual nozzles as cooling medium nozzles, which adapt the forced flow in accordance with the design of the reactor pressure vessel 14 in the floor area and generate the best possible forced flow, so that the greatest possible heat flow can be absorbed by the reactor pressure vessel 14.
- a particular advantage of the reactor pressure vessel cooling system is increased cooling of the reactor pressure vessel. As a result, however, more heat is also introduced into the cooling water, so that the cooling water temperature rises.
- a pressure relief device 38 is provided, which is arranged geodetically above the cooling water surface, i.e. above the second surface symbol 22 in the figure, and directs air or steam out of the containment vessel 12 into the environment. In this way, there is also a desired heat transfer of heat within the container 12 into the environment.
- a filter system 40 is provided in the pressure relief device 38.
- FIG. 2 1 shows in an example a second reactor pressure vessel cooling system 50 for a nuclear reactor of a nuclear power plant.
- the pumping device 24 conveys the cooling water through the supply line 34 first to a heat exchanger 52, which is designed, for example, as a water/water heat exchanger as part of a cooling medium heat exchanger system whose further components and parts are not shown in detail in the figure.
- the cooling water flows on to the nozzle head 36.
- the cooling water in the heat exchanger 52 is cooled by the drive liquid, for example water, of the drive turbine 28 in which the water line 30 supplies the drive liquid flowing out of the drive turbine 28 to a recooling side of the heat exchanger 52 and the drive fluid is conducted from there out of the containment vessel 12 again.
- the heat exchanger 52 is introduced into the reactor pressure vessel cooling system in addition to the pressure relief device 38 .
- the heat exchanger 52 can also be designed in such a way that the heat introduced into the cooling water by the reactor pressure vessel is completely absorbed by the heat exchanger or heat exchangers and transported out of the containment vessel 12 by its recooling. In this case, the amount of cooling water fed into the cooling water collection area 20 by the cooling water feed 42 could be greatly reduced or even eliminated entirely.
- the nozzle head 36 is again arranged in the same place in the sketch shown as in FIG figure 1 .
- the supply line 34 directs the cooling water to a large number of nozzle elements, which flow against the cooling water at different points on the surface of the bottom area or the middle area of the reactor pressure vessel 14 .
- This means that the cooling water does not have to flow onto the reactor pressure vessel 14 at one point, but can take place at a large number of points, which are also arranged, for example, in a ring around the bottom area of the reactor pressure vessel 14 or also in different geodetically spaced planes around the bottom area or the central region of the reactor pressure vessel 14 are arranged around.
- the arrangement can be ring-shaped or in other arrangement patterns.
- the 3 shows an example of a third reactor pressure vessel cooling system 60, in which the pump device 24 in turn supplies cooling water to the nozzle head 36 via the feed line 34.
- the cooling water jet from the nozzle head 36 is not directed directly at the reactor pressure vessel 14, but viewed in the geodetic direction downwards.
- a corresponding orientation of the nozzle head 36 also creates a forced flow in the cooling water of the cooling water collection area 20, which, however, does not impinge on the reactor pressure vessel 14 immediately after leaving the nozzle head, but first causes the cooling water in the cooling water collection area 20 to move, so that the reactor pressure vessel 14 flows indirectly through the in Movement offset cooling water is illuminated.
- Improved cooling of the reactor pressure vessel 14 is also achieved in this advantageous manner.
- the 4 shows an example of a fourth reactor pressure vessel cooling system 70, in which the nozzle head 36 is again directed downwards, so that the in figure 3 explained indirect or indirect forced flow in the cooling water of the cooling water collecting area 20 forms.
- the heat exchanger 52 is again interposed in the supply line 34 , so that the cooling water flowing through the supply line 34 to the nozzle head 36 is first cooled before it emerges from the nozzle head 36 .
- the heat exchanger 52 is shown in the figure above the cooling water level of the cooling water. However, it is also just as conceivable that the heat exchanger is partially or completely immersed in the cooling water. In this case, too, the cooling of the cooling water before it is fed to the nozzle head 36 is ensured.
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Description
Die Erfindung betrifft ein Reaktordruckbehälterkühlsystem einer kerntechnischen Anlage mit einem abgeschlossenen Sicherheitsbehälter, wobei innerhalb des Sicherheitsbehälters ein Reaktordruckbehälter angeordnet ist, wobei sich innerhalb des Sicherheitsbehälters ein Kühlmediumsammelbereich zur Aufnahme eines Kühlmediums befindet, und wobei zwischen dem Sicherheitsbehälter und dem Reaktordruckbehälter so viel Kühlmedium vorhanden ist, dass der Reaktordruckbehälter zumindest teilweise vom Kühlmedium umgeben ist.The invention relates to a reactor pressure vessel cooling system of a nuclear facility with a closed containment, with a reactor pressure vessel being arranged inside the containment, with a cooling medium collection area for receiving a cooling medium being located within the containment, and with so much cooling medium being present between the containment and the reactor pressure vessel that the reactor pressure vessel is at least partially surrounded by the cooling medium.
Es ist allgemein bekannt, dass in kerntechnischen Anlagen eine Vielzahl an Vorkehrungen zum Schutz der Umwelt vor möglichen Schäden eines eventuellen Störfalls getroffen wird. Ein Störfall kann mit einer erhöhten Temperaturentwicklung innerhalb eines Kernreaktors einhergehen, wenn die vorgesehenen Kernreaktor-Sicherheitskühlsysteme ausfallen. In solchen Fällen wird die reaktorseitig erzeugte Wärmeenergie, beispielsweise die Nachzerfallsleistung, nicht in genügendem Maße abgeführt und es kann zu einer Überhitzung des Kernreaktors kommen.It is generally known that a large number of precautions are taken in nuclear facilities to protect the environment from possible damage in the event of an accident. An accident can be accompanied by increased temperature development within a nuclear reactor if the planned nuclear reactor safety cooling systems fail. In such cases, the thermal energy generated on the reactor side, for example the decay output, is not dissipated to a sufficient extent and the nuclear reactor can overheat.
Um auch im Störfall ein Höchstmaß an Sicherheit zu gewährleisten, ist ein Kernreaktor von einem hermetisch abgeschlossenen Sicherheitsbehälter beziehungsweise einem Containment umgeben, wodurch beispielsweise im Falle eines Bruchs von aktivitätführenden Systemen, im Falle von defekten Brennstäben oder im Falle einer Kettenreaktion die dabei möglicherweise freigesetzten radioaktiven Stoffe nicht in die Umgebung austreten können, sondern vielmehr in dem Sicherheitsbehälter zurückgehalten werden. Derartige Sicherheitsbehälter können beispielsweise in Form einer Betonglocke realisiert sein. Innerhalb eines Sicherheitsbehälters ist ein Kühlmediumsammelbereich oder ein sogenannter Reaktorsumpf beziehungsweise ein Sumpfbereich vorgesehen, in welchem bei einem eventuellen Störfall beispielsweise aus einem leckenden Kühlsystem austretendes radioaktiv kontaminiertes Kühlwasser gesammelt, bedarfsweise gekühlt und dem Kühlsystem beziehungsweise dem Reaktorkern oder auch anderen Systemen wieder zugeführt wird. Es existieren auch Schutzkonzepte, bei welchen ein Kernreaktor in einem Kühlmediumsammelbereich angeordnet ist, welcher im Störfall mit Kühlwasser geflutet wird, um eine erhöhte Kühlung des Kernreaktors zu erzielen, wobei auch hier das sich im Reaktorsumpf ansammelnde radioaktiv kontaminierte Kühlwasser gekühlt werden muss, beispielsweise mit einem Sicherheitsbehälterkühlsystem gemäß der deutschen Patentanmeldung
Ein weiteres technisches Problem bei einem Störfall ist es, die Integrität, also die mechanische Stabilität sowie der Erhalt der materialtechnischen Eigenschaften eines Reaktordruckbehälters, nämlich der äußeren Hülle des Kernreaktors, zu erhalten. Hierfür ist das vorstehend genannte Fluten des Sicherheitsbehälters und damit des Reaktorsumpfes mit Kühlwasser ebenfalls gedacht. Auf diese Weise wird der Wärmeübergang und Wärmeabtransport von Wärme aus dem Reaktordruckbehälter auf das Kühlwasser verbessert im Vergleich von einem Wärmeübergang/Wärmeabtransport vom Reaktordruckbehälter auf die Umgebungsluft im Sicherheitsbehälter. Durch das Aufnehmen der Wärme durch das Kühlwasser steigt das erwärmte Kühlwasser nach oben und setzt so bestenfalls eine Naturkonvektion des Kühlwassers in Gang, die den Wärmeabtransport erhöht. Nachteilig bei diesem Stand der Technik ist es, dass für bestimmte Störfälle mit erhöhten Anfall von Wärme im Kernreaktor, zum Beispiel bei einer Kernschmelze, diese Art der Kühlung nicht mehr ausreicht, um die Integrität des Reaktordruckbehälters auf Dauer zu erhalten. Ausgehend von diesem Stand der Technik ist es Aufgabe der Erfindung, ein Reaktordruckbehälterkühlsystem anzugeben, mit dem die Kühlung eines Reaktordruckbehälters bei einem Störfall verbessert ist.Another technical problem in the event of an accident is maintaining the integrity, i.e. the mechanical stability and the preservation of the material properties of a reactor pressure vessel, namely the outer shell of the nuclear reactor. The aforementioned flooding of the containment and thus the reactor sump with cooling water is also intended for this purpose. In this way, the heat transfer and heat dissipation of heat from the reactor pressure vessel to the cooling water is improved compared to a heat transfer/heat dissipation from the reactor pressure vessel to the ambient air in the containment. As the heat is absorbed by the cooling water, the heated cooling water rises and at best sets natural convection of the cooling water in motion, which increases the heat dissipation. The disadvantage of this state of the art is that for certain incidents with increased accumulation of heat in the nuclear reactor, for example a core meltdown, this type of cooling is no longer sufficient to permanently maintain the integrity of the reactor pressure vessel. Proceeding from this prior art, it is the object of the invention to specify a reactor pressure vessel cooling system with which the cooling of a reactor pressure vessel is improved in the event of an accident.
Die Aufgabe wird gelöst durch ein Reaktordruckbehälterkühlsystem der eingangs genannten Art. Diese ist dadurch gekennzeichnet, dass im Sicherheitsbehälter eine Pumpvorrichtung angeordnet ist, die vollständig im Kühlmedium eingetaucht ist, dass durch die Pumpvorrichtung Kühlmedium einer Düsenanordnung zugeführt ist, dass die Düsenvorrichtung eine Anzahl von Kühlmediumdüsen aufweist, und dass die Kühlmediumdüsen so angeordnet sind, dass durch das durch die Kühlmediumdüsen strömende Kühlmedium eine Kühlmediumzwangsströmung im Kühlmedium des Kühlmediumsammelbereichs erzeugt ist, durch welche Kühlmediumzwangsströmung ein Oberflächenbereich des Reaktordruckbehälters angeströmt ist.The object is achieved by a reactor pressure vessel cooling system of the type mentioned at the outset. This is characterized in that a pumping device is arranged in the containment and is completely immersed in the cooling medium, that cooling medium is supplied to a nozzle arrangement by the pumping device, that the nozzle device has a number of cooling medium nozzles and that the cooling medium nozzles are arranged such that the cooling medium flowing through the cooling medium nozzles generates a forced cooling medium flow in the cooling medium of the cooling medium collecting area, through which forced cooling medium flow a surface area of the reactor pressure vessel flows.
Die Grundidee der Erfindung besteht darin, anstelle der bisherigen alleinigen Naturkonvektion nunmehr mittels einer Pumpvorrichtung eine Zwangsströmung im Kühlmedium zu erzeugen, die auf einen Oberflächenbereich des Reaktordruckbehälters gerichtet ist und derart den Wärmeabtransport vom Reaktordruckbehälter in das Kühlmedium im Vergleich zu den bisher bekannten Kühlsystemen erhöht. Die Kühlleistung beziehungsweise die Kühlung des Reaktordruckbehälters bei einem Störfall ist verbessert. Bei einem solchen Störfall, der für den Betrieb des erfindungsgemä-βen Reaktordruckbehälterkühlsystems unterstellt ist, wird der Sicherheitsbehälter, auch als Containment oder Confinement bezeichnet, mit Kühlmedium wenigstens zum Teil geflutet sein, wobei durch das Kühlmedium der Kühlmediumsammelbereich ausgebildet ist. Die Pumpvorrichtung ist bevorzugt geodätisch unterhalb eines geplanten Flüssigkeitsstandes des Kühlmediums nach dem Fluten im Sicherheitsbehälter angeordnet. Für den Betrieb des Reaktordruckbehälterkühlsystem ist es nämlich von Vorteil, dass die Pumpvorrichtung im Kühlmediumsammelbereich angeordnet ist, der im Betriebsfall geflutet ist, so dass die Pumpvorrichtung vollständig Kühlmedium eingetaucht ist und derart als Tauchpumpe oder Sumpfpumpe betrieben wird. Dies ist zwar nicht zwingend erforderlich, bessert jedoch die Fördereigenschaften der Pumpvorrichtung.The basic idea of the invention is, instead of the previous natural convection alone, to now generate a forced flow in the cooling medium by means of a pump device, which is directed to a surface area of the reactor pressure vessel and in this way increases the heat transport from the reactor pressure vessel into the cooling medium in comparison to the previously known cooling systems. The cooling capacity or the cooling of the reactor pressure vessel in the event of an accident is improved. In the event of such an accident, which is assumed for the operation of the reactor pressure vessel cooling system according to the invention, the safety vessel, also referred to as containment or confinement, will be at least partially flooded with cooling medium, with the cooling medium forming the cooling medium collection area. The pumping device is preferably arranged geodetically below a planned liquid level of the cooling medium after the flooding in the containment. For the operation of the reactor pressure vessel cooling system, it is advantageous that the pumping device is arranged in the cooling medium collection area, which is flooded during operation, so that the pumping device is completely immersed in cooling medium and is operated as a submersible pump or sump pump. Although this is not absolutely necessary, it improves the pumping properties of the pump device.
Ein Einsatzfall für das Reaktordruckbehälterkühlsystem ist ein Störfallszenario, bei dem eine Kernschmelze im Kernreaktor, also innerhalb des Reaktordruckbehälters eingetreten ist. Bisherige Kühlsysteme oder Notfallkühlsysteme beherrschen diesen Störfall nicht dauerhaft. Die Kernschmelze sammelt sich nämlich im geodätisch unteren Bereich des Reaktordruckbehälters und entfaltet dort eine vergleichsweise starke Wärmeentwicklung, die das Material beziehungsweise die Wandung des Reaktordruckbehälters materialtechnisch beansprucht. Mit dem erfindungsgemäßen Reaktordruckbehälterkühlsystem ist ein aktives Kühlsystem, also ein Kühlsystem mit einer Zwangsströmung, offenbart, welches insbesondere den von der Wärmeentwicklung im Reaktordruckbehälter unmittelbar betroffenen Bereich der Reaktordruckbehälterwand mit Kühlmedium beaufschlagt. Das Kühlmedium ist häufig Kühlwasser oder boriertes Kühlwasser. Der betreffende Wandbereich ist entsprechend gekühlt, so dass entsprechend mehr Wärme vom Reaktordruckbehälter wegtransportiert wird. Auf diese Weise ist ein unzulässiger Temperaturanstieg der Reaktordruckbehälterwand vermieden, der möglicherweise auch mit einem Verlust an Wandmaterial des Reaktordruckbehälters verbunden wäre. Eine erforderliche Wandstärke der Reaktordruckbehälterwand bleibt also vorteilhaft erhalten. Auch ein maximal zulässiger Wärmefluss über die Reaktordruckbehälterwand bleibt unterschritten. Beide Effekte tragen zum Erhalt der Integrität beziehungsweise Stabilität des Reaktordruckbehälters bei.One application for the reactor pressure vessel cooling system is an accident scenario in which a core meltdown has occurred in the nuclear reactor, i.e. inside the reactor pressure vessel. Previous cooling systems or emergency cooling systems have mastered this Incident not permanent. The core meltdown namely collects in the geodetically lower area of the reactor pressure vessel and unfolds there a comparatively strong development of heat, which stresses the material or the wall of the reactor pressure vessel in terms of material technology. With the reactor pressure vessel cooling system according to the invention, an active cooling system, ie a cooling system with a forced flow, is disclosed which applies cooling medium in particular to the region of the reactor pressure vessel wall directly affected by the heat generation in the reactor pressure vessel. The cooling medium is often cooling water or borated cooling water. The relevant wall area is correspondingly cooled, so that correspondingly more heat is transported away from the reactor pressure vessel. In this way, an impermissible rise in temperature of the reactor pressure vessel wall is avoided, which would possibly also be associated with a loss of wall material of the reactor pressure vessel. A required wall thickness of the reactor pressure vessel wall is thus advantageously retained. The maximum permissible heat flow over the reactor pressure vessel wall is also not reached. Both effects contribute to maintaining the integrity or stability of the reactor pressure vessel.
Dabei kann die Zwangsströmung grundsätzlich auf zwei möglichen Arten eingesetzt werden. Zum einen in der Art, dass das aus den Kühlmediumdüsen austretende Kühlmedium unmittelbar in Richtung der zu kühlenden Oberfläche des Reaktordruckbehälters gestrahlt wird. Zum andern in der Art, dass das aus den Kühlmediumdüsen austretende Kühlmedium in eine andere Richtung als in Richtung der zu kühlen Oberfläche des Reaktordruckbehälters gestrahlt wird, bevorzugt in die Richtung geodätisch nach unten. Eine besonders günstige Richtung für die zweite Art der Zwangsströmung lässt sich durch empirische Untersuchungen im Einzelfall für eine vorhandene Reaktordruckbehältergeometrie ermitteln oder mit einem Strömungsmodell für eine vorhandene Reaktordruckbehältergeometrie am Computer berechnen. Diese zweite Art soll auch mittelbare Zwangsströmung genannt werden.The forced flow can basically be used in two possible ways. On the one hand in such a way that the cooling medium emerging from the cooling medium nozzles is jetted directly in the direction of the surface of the reactor pressure vessel to be cooled. On the other hand in the way that the cooling medium emerging from the cooling medium nozzles is jetted in a direction other than in the direction of the surface of the reactor pressure vessel to be cooled, preferably in the geodetically downward direction. A particularly favorable direction for the second type of forced flow can be determined by empirical investigations in individual cases for an existing reactor pressure vessel geometry or calculated on the computer using a flow model for an existing reactor pressure vessel geometry. This second type should also be called indirect forced flow.
Eine alternative Ausgestaltung des Reaktordruckbehälterkühlsystem ist dadurch gekennzeichnet, dass die Kühlmediumdüsen vollständig von Kühlmedium umgeben sind. Auf diese Weise ist sichergestellt, dass eine Zwangsströmung mit möglichst vorteilhaften Kühleffekten erzeugt ist. Der Volumenstrom der Zwangsströmung ist nämlich beim vollständigem Eintauchen der Kühlmediumdüsen in das Kühlmedium erhöht, da das umgebende Kühlmedium von dem Kühlmediumstrahl aus den Kühlmediumdüsen mitgerissen wird und so einen erhöhten Volumenstrom und damit einen ebenfalls erhöhten Kühleffekt auf den Reaktordruckbehälter bewirkt.An alternative configuration of the reactor pressure vessel cooling system is characterized in that the cooling medium nozzles are completely surrounded by cooling medium. In this way it is ensured that a forced flow is generated with the most advantageous possible cooling effects. The volume flow of the forced flow is namely when the cooling medium nozzles are completely immersed in the cooling medium, since the surrounding cooling medium is entrained by the cooling medium jet from the cooling medium nozzles and thus causes an increased volume flow and thus also an increased cooling effect on the reactor pressure vessel.
Bei einem vorteilhaft ausgestalteten Reaktordruckbehälterkühlsystem ist wenigstens ein Teil der Kühlmediumdüsen so ausgerichtet, dass das durch sie austretente Kühlmedium in Richtung Reaktordruckbehälter geleitet ist. Auf diese Weise ist ein bestimmter Oberflächenbereich des Reaktordruckbehälters, der beispielsweise besonders von der Wärmeentwicklung einer Kernschmelze unmittelbar betroffen ist, gezielt kühlbar, nämlich durch das unmittelbare Anstrahlen mit Kühlwasser. Auf diese Weise ist es besonders leicht möglich das Reaktordruckbehälterkühlsystem auf verschiedene Ausgestaltungen des Bodenbereichs des Reaktordruckbehälters anzupassen. Es gibt nämlich nicht nur klöpperbodenähnliche oder sphärische Formen von Reaktordruckbehälterböden, sondern auch elliptische Formen und weitere, zum Beispiel asymmetrische Bodenformen.In an advantageously configured reactor pressure vessel cooling system, at least some of the cooling medium nozzles are aligned in such a way that the cooling medium exiting through them is guided in the direction of the reactor pressure vessel. In this way, a specific surface area of the reactor pressure vessel, which is directly affected, for example, by the heat generated by a core meltdown, can be cooled in a targeted manner, namely by direct jetting with cooling water. In this way, it is particularly easy to adapt the reactor pressure vessel cooling system to different configurations of the bottom area of the reactor pressure vessel. In fact, there are not only dished-end-like or spherical shapes of reactor pressure vessel heads, but also elliptical shapes and other, for example asymmetrical, bottom shapes.
Bei einem Reaktordruckbehälterkühlsystem, das vorsieht, dass wenigstens ein Teil der Kühlmediumdüsen so ausgerichtet ist, dass das durch sie austretente Kühlmedium im Wesentlich in geodätischer Richtung nach unten geleitet ist, und dass durch die so entstehende mittelbare Zwangsströmung der Reaktordruckbehälter angeströmt ist. Auf diese Weise ist eine besonders einfache und robuste Zwangskühlung realisiert, wobei mit der mittelbaren Zwangsströmung praktisch der gesamte Oberflächenbereich des Reaktordruckbehälters, der in das Kühlmedium eingetaucht ist, kühlbar ist. Zudem ist der Kühleffekt unabhängig vom Flüssigkeitsstand des Kühlmediums im Sicherheitsbehälter jeweils im vorhandenen Kühlmedium gegeben.In a reactor pressure vessel cooling system, which provides that at least some of the cooling medium nozzles are aligned in such a way that the cooling medium exiting through them is guided essentially downwards in the geodetic direction, and that the resulting indirect forced flow flows against the reactor pressure vessel. In this way, a particularly simple and robust forced cooling is realized, with the indirect forced flow being able to cool practically the entire surface area of the reactor pressure vessel that is immersed in the cooling medium. In addition, the cooling effect is given in the existing cooling medium, regardless of the liquid level of the cooling medium in the containment.
In einer alternativen Ausgestaltung des Reaktordruckbehälterkühlsystems sind die Kühlmediumdüsen zu wenigstens einem Düsenring angeordnet. Zudem ist der wenigstens eine Düsenring um den geodätisch unteren Bodenbereich des Reaktordruckbehälters und/oder einem mittleren, geodätisch oberhalb vom Bodenbereich gelegenen Mittelbereich des Reaktordruckbehälters angeordnet. Auf diese Weise lassen sich bestimmte Oberflächenbereiche des Reaktordruckbehälters gezielt mit Kühlmedium anstrahlen und zudem die Menge oder der Volumenstrom von Kühlmedium für bestimmte Oberflächenbereiche durch die Auslegung der Kühlmediumdüsen und des wenigstens einen Düsenrings bestimmen. Es ist auch innerhalb des Erfindungsgedankens, dass einzelne Kühlmediumdüsen oder Gruppen von Kühlmediumdüsen eine unterschiedliche Auslegung haben, so dass eine unterschiedliche Menge von Kühlmedium bei einem durch die Pumpvorrichtung vorgegebenen Druck durch die Kühlmediumdüsen fließt.In an alternative configuration of the reactor pressure vessel cooling system, the cooling medium nozzles are arranged in at least one nozzle ring. In addition, the at least one nozzle ring is arranged around the geodetically lower base area of the reactor pressure vessel and/or a central central area of the reactor pressure vessel located geodetically above the base area. In this way, certain surface areas of the reactor pressure vessel can be specifically irradiated with cooling medium and also the quantity or the volume flow of cooling medium determined for specific surface areas by the design of the cooling medium nozzles and the at least one nozzle ring. It is also within the scope of the invention that individual coolant nozzles or groups of coolant nozzles have a different design, so that a different amount of coolant flows through the coolant nozzles at a pressure predetermined by the pump device.
Ein weiteres Reaktordruckbehälterkühlsystem sieht vor, dass durch die Pumpvorrichtung Kühlmedium zu weiteren Kühlmediumdüsen geleitet ist, mittels welcher weiterer Kühlmediumdüsen Kühlmedium geodätisch oberhalb des Kühlmediums im Sicherheitsbehälter bedarfsweise in die Luft im Sicherheitsbehälter versprühbar ist. Auf diese Weise wird dem oberhalb des Kühlmediums gelegenen Bereich im Sicherheitsbehälter zusätzlich Wärme entzogen und vom Kühlmedium aufgenommen. Auch der Reaktordruckbehälterbereich oberhalb des Kühlmediums ist so mit Kühlmedium besprühbar. Die Kühlleistung für den Reaktordruckbehälter ist hierdurch weiter erhöht.A further reactor pressure vessel cooling system provides that cooling medium is routed through the pumping device to further cooling medium nozzles, by means of which further cooling medium nozzles cooling medium can be sprayed geodetically above the cooling medium in the containment as required into the air in the containment. In this way, additional heat is extracted from the area in the containment above the cooling medium and absorbed by the cooling medium. The reactor pressure vessel area above the cooling medium can also be sprayed with cooling medium in this way. This further increases the cooling capacity for the reactor pressure vessel.
Des Weiteren ist es für das Reaktordruckbehälterkühlsystem vorgesehen, dass zwischen der Pumpvorrichtung und den Kühlmediumdüsen ein Kühlmediumwärmetauschersystem angeordnet ist, mittels welchem Wärme von innerhalb des Sicherheitsbehälters nach außerhalb des Sicherheitsbehälters transportierbar ist. Derart ist ein zusätzliches Kühlsystem beziehungsweise Rückkühlsystem für das Kühlmedium geschaffen, dass zusätzlich zu den sowieso vorhandenen Wärmetauschern eines Sicherheitsbehälterkühlsystem arbeitet. Auf diese Weise wird auch die Rückkühlleistung des Kühlmediums weiter erhöht. Zudem ist die Temperatur des Kühlmediums welches durch die Zuleitung den Kühlmediumdüsen zugeführt wird durch wenigstens einen Kühlmediumwärmetauscher des Kühlmediumwärmetauschersystems verringert, so dass jedenfalls auch eine verbesserte Kühlleistung für die Reaktordruckbehälterwand bewirkt ist.Furthermore, it is provided for the reactor pressure vessel cooling system that a cooling medium heat exchanger system is arranged between the pump device and the cooling medium nozzles, by means of which heat can be transported from inside the containment to outside the containment. In this way, an additional cooling system or recooling system for the cooling medium is created that works in addition to the heat exchangers of a containment cooling system that are present anyway. In this way, the re-cooling capacity of the cooling medium is further increased. In addition, the temperature of the cooling medium which is supplied to the cooling medium nozzles through the feed line is reduced by at least one cooling medium heat exchanger of the cooling medium heat exchanger system, so that in any case an improved cooling capacity for the reactor pressure vessel wall is also achieved.
Dabei ist es auch möglich, dass das Kühlmediumwärmetauschersystem geodätisch oberhalb des Kühlmediumsammelbereiches angeordnet ist, so dass das Kühlmediumwärmetauschersystem im Betriebsfall geodätisch oberhalb des Kühlmediums angeordnet ist.It is also possible that the cooling medium heat exchanger system is arranged geodetically above the cooling medium collecting area, so that the cooling medium heat exchanger system is arranged geodetically above the cooling medium during operation.
In einer weiteren vorteilhaften Ausgestaltung des Reaktordruckbehälterkühlsystems ist dadurch erreicht, dass der Sicherheitsbehälter eine Druckentlastungsvorrichtung aufweist, die mit einer Kühlmediumzufuhreinrichtung zusammenarbeitet, welche Kühlmediumzufuhreinrichtung von einer Stelle außerhalb des Sicherheitsbehälters Kühlmedium in einer Menge in den Sicherheitsbehälter einleitet, wie durch die Druckentlastungsvorrichtung Kühlmedium von innerhalb des Sicherheitsbehälters nach außerhalb gelangt. Auf diese Weise ist ein zusätzlicher Kühleffekt für das Kühlmedium erreichbar, in dem Kühlwasser verdampft und hierdurch Verdampfungswärme aufnimmt. Das verdampfte Kühlwasser wird durch die Druckentlastungsvorrichtung, gegebenenfalls unter Zwischenschaltung eines Filtersystems zur Zurückhaltung radioaktiver Stoffe nach außerhalb des Sicherheitsbehälters geleitet. Die durch Verdampfen reduzierte Kühlmediummenge wird entsprechend ergänzt durch die Zufuhr von Kühlmedium von einer Stelle außerhalb des Sicherheitsbehälters in den Sicherheitsbehälter hinein.In a further advantageous embodiment of the reactor pressure vessel cooling system, the result is that the containment has a pressure relief device which works together with a coolant supply device, which coolant supply device introduces cooling medium into the containment from a point outside of the containment in a quantity such as through the pressure relief device cooling medium from inside the containment got outside. In this way, an additional cooling effect for the cooling medium can be achieved, in which the cooling water evaporates and thereby absorbs evaporation heat. The vaporized cooling water is routed through the pressure relief device to the outside of the containment, optionally with the interposition of a filter system for retaining radioactive substances. The amount of cooling medium reduced by evaporation is supplemented accordingly by the supply of cooling medium from a point outside the containment into the containment.
Als Pumpen oder Pumpenelemente für die Pumpvorrichtung kommen insbesondere Strahlpumpen, Kreiselpumpen, volumetrisch arbeitende Pumpen oder Kolbenpumpen in Betracht. Diese werden vorzugsweise von elektrisch oder hydraulisch betriebenen Antrieben oder von einer hydraulisch betriebenen Turbine angetrieben.In particular, jet pumps, centrifugal pumps, volumetric pumps or piston pumps come into consideration as pumps or pump elements for the pump device. These are preferably driven by electrically or hydraulically operated drives or by a hydraulically operated turbine.
Vorteilhaft ist es, wenn eine Antriebsflüssigkeit des hydraulisch betriebenen Antriebs oder der hydraulisch betriebenen Turbine von einer Pumpe gefördert ist, die außerhalb des Sicherheitsbehälters angeordnet ist. Hierdurch ist sichergestellt, dass die Pumpe außerhalb des vom Störfall betroffenen Bereichs betrieben werden kann. Auf diese Weise ist es auch möglich die Pumpe als konventionell angetriebene Pumpe, zum Beispiel als elektrisch oder mit Verbrennungsmotor angetriebene Pumpe auszugestalten. Auch entsprechende Redundanzen für die Pumpe können dann auf besonders einfache Weise realisiert werden.It is advantageous if a drive fluid of the hydraulically operated drive or the hydraulically operated turbine is delivered by a pump that is arranged outside of the containment vessel. This ensures that the pump can be operated outside the area affected by the incident. In this way it is also possible to design the pump as a conventionally driven pump, for example as an electrically driven pump or as a pump driven by an internal combustion engine. Corresponding redundancies for the pump can then also be implemented in a particularly simple manner.
Zudem ist es vorteilhaft, wenn die Antriebsflüssigkeit das Kühlmedium für das Kühlmediumwärmetauschersystem ist. Die Kühlleistung des Reaktordruckbehälterkühlsystem mit nämlich weiter erhöht, ohne dass eine zusätzliche Pumpe für das Kühlmediumwärmetauschersystem erforderlich wäre.In addition, it is advantageous if the drive fluid is the cooling medium for the cooling medium heat exchanger system. The cooling capacity of the reactor pressure vessel cooling system is further increased without requiring an additional pump for the cooling medium heat exchanger system.
Alle genannten Ausgestaltungen des Reaktordruckbehälterkühlsystems sind so auslegbar, dass die Kühlung des Reaktordruckbehälters so erhöht ist, dass diese ausreicht auch den Anfall von Wärme im Kernreaktor, zum Beispiel bei einer Kernschmelze, auch auf Dauer von zum Beispiel 3 bis 6 Monaten oder auch Jahre, abzutransportieren, so dass die Integrität des Reaktordruckbehälters entsprechend dauerhaft erhalten bleibt.All the configurations of the reactor pressure vessel cooling system mentioned can be designed in such a way that the cooling of the reactor pressure vessel is increased in such a way that it is also sufficient to transport away the heat generated in the nuclear reactor, for example in the event of a core meltdown, even over a period of, for example, 3 to 6 months or even years , so that the integrity of the reactor pressure vessel is permanently maintained.
Weitere vorteilhafte Ausgestaltungsmöglichkeiten sind den weiteren abhängigen Ansprüchen zu entnehmen.Further advantageous configuration options can be found in the further dependent claims.
Anhand der in den Zeichnungen dargestellten Ausführungsbeispiele sollen die Erfindung, weitere Ausführungsformen und weitere Vorteile näher beschrieben werden.The invention, further embodiments and further advantages are to be described in more detail on the basis of the exemplary embodiments illustrated in the drawings.
Es zeigen
- Fig. 1
- ein erstes Beispiel für ein Reaktordruckbehälterkühlsystem,
- Fig. 2
- ein zweites Beispiel für ein Reaktordruckbehälterkühlsystem,
- Fig. 3
- ein drittes Beispiel für ein Reaktordruckbehälterkühlsystem sowie
- Fig. 4
- ein viertes Beispiel für ein Reaktordruckbehälterkühlsystem.
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- a first example of a reactor pressure vessel cooling system,
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- a second example of a reactor pressure vessel cooling system,
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- a third example of a reactor pressure vessel cooling system and
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- a fourth example of a reactor pressure vessel cooling system.
Für den hier gezeigten Störfall bei dem eine Kernschmelze eingetreten ist, konzentriert sich eine Wärmeentwicklung des Kernmaterials innerhalb des Reaktordruckbehälters 14 insbesondere im Sammelbereich 16. Von dort aus wird, aufgrund des treibenden Temperaturgefälles, ein Wärmestrom insbesondere durch das Material des Reaktordruckbehälters 14 in das Kühlwasser geleitet. Der vom Wärmestrom besonders belastete Teil des Reaktordruckbehälters 14 muss dabei vollständig vom Kühlwasser umgeben sein, um einen möglichst guten Wärmeübergang der Wärme an das Kühlwasser zu erreichen. Ein Temperaturanstieg, insbesondere einen unzulässigen Temperaturanstieg des Reaktordruckbehälters 14 in dem betroffenen Bereich ist durch das Reaktordruckbehälterkühlsystem zu vermeiden. Die Folgen eines unzulässigen Temperaturanstiegs wären zum Beispiel Verschlechterung der Material- und Stabilitätseigenschaften des Reaktordruckbehälters 14 bis hin zum Materialversagen, zum Beispiel Materialabtrag an der Reaktordruckbehälterwand oder Verringerung beziehungsweise Zerstörung der Integrität des Reaktordruckbehälters 14.For the accident shown here, in which a core meltdown has occurred, heat development of the core material is concentrated within the
Im Kühlwassersammelbereich 22 als Kühlmediumsammelbereich ist eine Pumpvorrichtung 24 angeordnet, die vollständig von Kühlwasser umgeben ist. Die. Pumpvorrichtung 24 weist eine Kreiselpumpe 26 als Pumpenelement sowie eine hydraulische Antriebsturbine 28 auf, die auf einer gemeinsamen Welle angeordnet sind. Eine solche Pumpvorrichtung ist beispielsweise in der deutschen Patentanmeldung
Ein besonderer Vorteil des Reaktordruckbehälterkühlsystem ist also eine gesteigerte Kühlung des Reaktordruckbehälters. Hierdurch wird jedoch auch mehr Wärme in das Kühlwasser eingetragen, so dass die Kühlwassertemperatur ansteigt. Zur Begrenzung des Kühlwassertemperaturanstiegs ist eine Druckentlastungsvorrichtung 38 vorgesehen, die geodätisch oberhalb der Kühlwasseroberfläche, also in der Figur oberhalb des zweiten Oberflächensymbols 22 angeordnet ist und Luft beziehungsweise Dampf aus dem Sicherheitsbehälter 12 hinaus in die Umgebung leitet. Auf diese Weise findet auch ein gewünschter Wärmetransport von Wärme innerhalb des sich als Behälters 12 in die Umgebung statt. Zur Rückhaltung von möglicherweise schädlichen oder radioaktiven Stoffen, die bei einem solchen Störfallszenario im Sicherheitsbehälter 12 vorhanden sein können, ist ein Filtersystem 40 in der Druckentlastungsvorrichtung 38 vorgesehen. Zudem ist zur Ergänzung von Kühlwasser, dass durch die Druckentlastungsvorrichtung 38 dem Sicherheitsbehälter 12 entnommen ist, eine Kühlwasserzufuhr 42 oder Kühlwasserzufuhrvorrichtung vorhanden, die in dem Maße Kühlwasser dem Sicherheitsbehälter 12 zuführt, wie durch die Druckentlastungsvorrichtung 38 entweicht.A particular advantage of the reactor pressure vessel cooling system is increased cooling of the reactor pressure vessel. As a result, however, more heat is also introduced into the cooling water, so that the cooling water temperature rises. To limit the increase in cooling water temperature, a
In
Der Düsenkopf 36 ist in der gezeigten Skizze wiederum an derselben Stelle angeordnet wie in der
Die
Die
- 1010
- erstes Reaktordruckbehälterkühlsystemfirst reactor pressure vessel cooling system
- 1212
- Sicherheitsbehältersecurity container
- 1414
- Reaktordruckbehälterreactor pressure vessel
- 1616
- Sammelbereichcollection area
- 1818
- erstes Oberflächensymbolfirst surface icon
- 2020
- Kühlwassersammelbereichcooling water collection area
- 2222
- zweites Oberflächensymbolsecond surface icon
- 2424
- Pumpvorrichtungpumping device
- 2626
- Kreiselpumpecentrifugal pump
- 2828
- Antriebsturbinedrive turbine
- 3030
- Wasserleitungwater pipe
- 3232
- Pumpepump
- 3434
- Zuleitungsupply line
- 3636
- erster Düsenkopffirst nozzle head
- 3838
- Druckentlastungsvorrichtungpressure relief device
- 4040
- Filtersystemfilter system
- 4242
- Kühlwasserzufuhrcooling water supply
- 5050
- zweites Reaktordruckbehälterkühlsystemsecond reactor pressure vessel cooling system
- 5252
- Wärmetauscherheat exchanger
- 6060
- drittes Reaktordruckbehälterkühlsystemthird reactor pressure vessel cooling system
- 7070
- viertes Reaktordruckbehälterkühlsystemfourth reactor pressure vessel cooling system
- 7272
- Pfeilearrows
Claims (12)
- Reactor pressure vessel-cooling system (10, 50, 60, 70) of a nuclear installation, having a sealed containment vessel (12), wherein a reactor pressure vessel (14) is arranged within the containment vessel (12), wherein a cooling-medium-collecting region (20) for receiving a cooling medium is situated within the containment vessel (12), wherein, between the containment vessel (12) and the reactor pressure vessel (14), there is so much cooling medium present that the reactor pressure vessel (14) is at least partially surrounded by cooling medium,
characterized
in that, in the containment vessel (12), there is arranged a pump apparatus (24) which is completely immersed in the cooling medium, in that cooling medium is fed to a nozzle apparatus by way of the pump apparatus (24), in that the nozzle apparatus has a number of cooling-medium nozzles, and in that the cooling-medium nozzles are arranged in such a way that, by way of the cooling medium flowing through the cooling-medium nozzles, a cooling-medium forced flow is generated in the cooling medium of the cooling-medium-collecting region, by way of which cooling-medium forced flow a surface region of the reactor pressure vessel is flowed against. - Reactor pressure vessel-cooling system (10, 50, 60, 70) according to Claim 1, characterized in that the cooling-medium nozzles are completely surrounded by cooling medium.
- Reactor pressure vessel-cooling system (10, 50, 60, 70) according to Claim 1 or 2, characterized in that at least a portion of the cooling-medium nozzles is oriented in such a way that the cooling medium emerging therethrough is directed in the direction of the reactor pressure vessel (14).
- Reactor pressure vessel-cooling system (10, 50, 60, 70) according to one of the preceding claims, characterized in that at least a portion of the cooling-medium nozzles is oriented in such a way that the cooling medium emerging therethrough is directed substantially downwards in the geodetic direction, and in that, by way of the indirect forced flow thus generated, the reactor pressure vessel (14) is flowed against.
- Reactor pressure vessel-cooling system (10, 50, 60, 70) according to one of the preceding claims, characterized in that the cooling-medium nozzles are arranged to form at least one nozzle ring, and in that the at least one nozzle ring is arranged around the geodetically lower bottom region of the reactor pressure vessel (14) and/or a central middle region of the reactor vessel (14), which middle region is situated geodetically above the bottom region.
- Reactor pressure vessel-cooling system (10, 50, 60, 70) according to one of the preceding claims, characterized in that, by way of the pump apparatus (24), cooling medium is directed to further cooling-medium nozzles, by means of which further cooling-medium nozzles cooling medium is able to sprayed geodetically above the cooling medium in the containment vessel (12) according to requirement.
- Reactor pressure vessel-cooling system (10, 50, 60, 70) according to one of the preceding claims, characterized in that, between the pump apparatus (24) and the cooling-medium nozzles, there is arranged a cooling-medium heat-exchanger system, by means of which heat is able to be transported from within the containment vessel (12) to outside the containment vessel (12).
- Reactor pressure vessel-cooling system (10, 50, 60, 70) according to Claim 7, characterized in that the cooling-medium heat-exchanger system is arranged geodetically above the cooling-medium-collecting region, so that the cooling-medium heat-exchanger system is arranged geodetically above the cooling medium during operation.
- Reactor pressure vessel-cooling system (10, 50, 60, 70) according to one of the preceding claims, characterized in that the containment vessel (12) has a pressure-relief apparatus (38) which interacts with a cooling-medium feed device, which cooling-medium feed device, from a point outside the containment vessel (12), introduces an amount of cooling medium into the containment vessel (12) according to cooling medium passing from within the containment vessel to the outside by way of the pressure-relief device (38).
- Reactor pressure vessel-cooling system (10, 50, 60, 70) according to one of the preceding claims, characterized in that the pump apparatus (24) has a jet pump, a centrifugal pump, a volumetric pump or a piston pump as pump element (26), and in that the pump element (26) is driven by an electrically or a hydraulically operated drive or by a hydraulically operated turbine.
- Reactor pressure vessel-cooling system (10, 50, 60, 70) according to Claim 10, characterized in that a pump (32) is arranged outside the containment vessel (12) as a conveying apparatus for the electrically or the hydraulically operated drive or for the hydraulically operated turbine.
- Reactor pressure vessel-cooling system (10, 50, 60, 70) according to Claim 11, characterized in that a driving liquid of the pump apparatus (24) is the cooling medium for the cooling-medium heat-exchanger system.
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE102019004244.1A DE102019004244B3 (en) | 2019-06-14 | 2019-06-14 | Reactor pressure vessel cooling system |
PCT/EP2020/000097 WO2020249252A1 (en) | 2019-06-14 | 2020-05-20 | Reactor pressure vessel cooling system |
Publications (2)
Publication Number | Publication Date |
---|---|
EP3984046A1 EP3984046A1 (en) | 2022-04-20 |
EP3984046B1 true EP3984046B1 (en) | 2023-07-05 |
Family
ID=71527739
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
EP20737358.0A Active EP3984046B1 (en) | 2019-06-14 | 2020-05-20 | Reactor pressure vessel cooling system |
Country Status (4)
Country | Link |
---|---|
EP (1) | EP3984046B1 (en) |
DE (1) | DE102019004244B3 (en) |
UA (1) | UA126846C2 (en) |
WO (1) | WO2020249252A1 (en) |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE102021002515B3 (en) | 2021-05-12 | 2022-05-19 | Westinghouse Electric Germany Gmbh | containment cooling system |
Family Cites Families (10)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
DE2346483A1 (en) * | 1973-09-14 | 1975-03-27 | Kraftwerk Union Ag | Sump pump assembly - for e.g. pressure water nuclear reactor with closed safety envelope |
JPH0792515B2 (en) * | 1988-11-16 | 1995-10-09 | 株式会社日立製作所 | Containment vessel |
JP2507694B2 (en) * | 1990-09-17 | 1996-06-12 | 株式会社日立製作所 | Nuclear reactor equipment |
US5295169A (en) * | 1990-10-15 | 1994-03-15 | Hitachi, Ltd. | Reactor containment facilities |
US5319687A (en) * | 1993-07-30 | 1994-06-07 | Westinghouse Electric Corp. | Device for preventing melt-through of a reactor vessel |
KR100204188B1 (en) * | 1995-08-08 | 1999-06-15 | 김세종 | Reactor lower vessel wall cooling method under severe accident of nuclear power plants and the device for the same |
FR2922678A1 (en) * | 2007-10-22 | 2009-04-24 | Commissariat Energie Atomique | NUCLEAR REACTOR WITH IMPROVED COOLING IN ACCIDENT CONDITIONS |
DE102017008253B3 (en) * | 2017-09-01 | 2018-12-06 | Westinghouse Electric Germany Gmbh | Containment cooling system |
DE102017008254A1 (en) * | 2017-09-01 | 2019-03-07 | Westinghouse Electric Germany Gmbh | Containment cooling system |
DE102018009260A1 (en) | 2018-11-24 | 2020-05-28 | Westinghouse Electric Germany Gmbh | Pumping device |
-
2019
- 2019-06-14 DE DE102019004244.1A patent/DE102019004244B3/en active Active
-
2020
- 2020-05-20 WO PCT/EP2020/000097 patent/WO2020249252A1/en active Application Filing
- 2020-05-20 UA UAA202105699A patent/UA126846C2/en unknown
- 2020-05-20 EP EP20737358.0A patent/EP3984046B1/en active Active
Also Published As
Publication number | Publication date |
---|---|
UA126846C2 (en) | 2023-02-08 |
WO2020249252A1 (en) | 2020-12-17 |
DE102019004244B3 (en) | 2020-10-01 |
EP3984046A1 (en) | 2022-04-20 |
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